Reactor primary loop coolant flow field, temperature field and stress field coupling calculation method
A technology of coolant flow and calculation method, which is applied in the field of nuclear power to achieve the effect of ensuring safe and stable operation
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Publication Date
- 2020-06-09
Smart Images

Figure 1 
Figure 2 
Figure 3
Abstract
Description
technical field
[0001] The invention belongs to the technical field of nuclear power, and relates to a coupling calculation method for a reactor primary circuit coolant flow field, a temperature field and a stress field. Background technique
[0002] The primary circuit coolant of the nuclear power plant reactor is used to cool the core of the nuclear reactor, absorb the heat released by the fission of the nuclear fuel in the reactor, control the reaction rate of the reactor, and transfer the heat to the secondary circuit medium to drive the turbogenerator to generate power. During the normal operation of the reactor, the working fluid state parameters of the reactor coolant directly determine the operating state of the reactor core, and are the key parameters for ensuring the safe and stable operation of the nuclear reactor.
[0003] The primary circuit system of the nuclear power plant is enclosed in a pressure vessel, which constitutes the pressure boundary of the primary...
Examples
Embodiment Construction
[0043] The present invention is described in further detail below in conjunction with accompanying drawing:
[0044] refer tofigure 1 and figure 2 , the reactor primary loop coolant flow field, temperature field and stress field coupling calculation method of the present invention comprises the following steps:
[0045] 1) According to the high temperature gas-cooled reactor core and steam generator drawings, use the CAD modeling tool embedded in cmosol to construct the high temperature gas-cooled reactor core model and steam generator model with the same size as the actual equipment, among which, image 3 is the geometric model of the reactor core, Figure 4 is the geometric model of the steam generator, in which, for the fast convergence of the computational domain, the characteristics of symmetric structures are applied, image 3 The middle geometry is a Mitsubishi prism, and its volume is 1 / 30 of the actual stack volume; Figure 4 The internal heat transfer tube struct...